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Suzuki, Satoshi; Enoeda, Mikio; Hatano, Toshihisa; Hirose, Takanori; Hayashi, Kimio; Tanigawa, Hisashi; Ochiai, Kentaro; Nishitani, Takeo; Tobita, Kenji; Akiba, Masato
Nuclear Fusion, 46(2), p.285 - 290, 2006/02
Times Cited Count：2 Percentile：7.02(Physics, Fluids & Plasmas)This paper presents significant progress in R&D of key technologies on the water-cooled solid breeder blanket for the ITER-TBM in JAERI. By the improvement of heat treatment process for blanket module fabrication, a fine-grained microstructure of F82H, can be obtained by homogenizing it at 1150 
C followed by normalizing at 930 C after the HIP process. Moreover, a promising bonding process for a tungsten armor and an F82H structural material was developed by using a uniaxial hot compression without any artificial compliant layer. Also, it has been confirmed that a fatigue lifetime correlation, which was developed for ITER divertor, can be applicable for F82H first wall mock-up. As for R&D on a breeder material, Li
TiO
, the effect of compression loads on thermal conductivity of pebble beds has been clarified. JAERI have extensively developed key technologies for ITER-TBM, and now steps up into an engineering R&D stage, where integrated performance of TBM structures will be demonstrated by scalable mock-ups.
Sato, Satoshi; Ochiai, Kentaro; Konno, Chikara; Tanigawa, Hisashi; Hirose, Takanori; Enoeda, Mikio
no journal, ,
Shutdown dose rates have been calculated for the ITER JA Water-Cooled Ceramic Breeder Test Blanket Module (WCCB-TBM) port using the partial model. The "Direct 1-Step Monte Carlo" (D1S) method is adopted for the decay 
-ray dose rate calculation. The decay photons are emitted from only TBM and we calculate the shutdown dose rates due to decay photons from the only TBM. Dose rates in front of the TBM in 1 month, 1 year and 1.5 year after irradiation are 300, 100 and 70 Sv/h, respectively, and they are too high. Dose rates behind the TBM in 1 month, 1 year and 1.5 year after irradiation are 5, 1 and 0.6 Sv/h, respectively, and they are also high. In future, nuclear analyses will be performed using the ITER global model.
Kawamura, Yoshinori
no journal, ,
The most important subject in the ITER-TBM test program is the estimation of TBR based on the information of neutron entered into TBM and of tritium recovered from TBM, and is the showing good prospect of TBR for DEMO. To discuss TBR estimation method in TBM test program, JAEA is carrying out the tritium generation and recovery experiments using simulated blanket at Fusion Neutron Source facility (FNS). At FNS, more accurate TBR estimation is possible by the comparison among the amount of calculated tritium generation, observed tritium generation, and tritium recovery. In the case of TBM, the neutron estimation is not so easy, because neutron source is a heterogeneous plasma having volume, and the plasma is generated in the form of pulses. So, TBR estimation in TBM program will need more effort.
Kawamura, Yoshinori; Hirose, Takanori; Tanigawa, Hisashi; Nakajima, Motoki; Gwon, H.; Miyata, Satoru; Sato, Satoshi
no journal, ,
Japan Domestic Agency (JADA) participates to the Test Blanket Module (TBM) test program of the ITER project as the lead party of Water Cooled Ceramic Breeder (WCCB) - TBM. We have signed TBM arrangement (TBMA) in Nov. 2014, and conceptual design has been reviewed in Feb. 2015. We have received 3 Cat-1 chits. Solution of Cat-1 chit is necessary to advance to the next design phase (preliminary design). Other intrinsic topic is the study on flow-accelerated corrosion of F82H. F82H is one of Reduced Activation Ferritic/Martensitic steels (RAFM) developed in Japan. In the piping of water cooling system, both F82H and stainless steel are used. As for fission reactor, there are many reports about corrosion of stainless steel. However, the report about F82H, especially flow-accelerated corrosion, is few. So, in this report, we will mainly show the situation for chit resolution, and the progress of the study on flow-accelerated corrosion of F82H.
